Оценка состояния графитовых материалов при облучении в ядерном реакторе; Материалы и технологии новых поколений в современном материаловедении
| Parent link: | Материалы и технологии новых поколений в современном материаловедении.— 2016.— [С. 79-84] |
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| Autor principal: | |
| Autor Corporativo: | |
| Outros Autores: | , |
| Resumo: | Заглавие с титульного экрана The paper provides guidance on the reprocessing of irradiated graphite in a lowtemperature plasma. The composition and properties of irradiated graphite of water- graphite reactors are considered. An assessment of the state of the graphitic material with long-term exposure in a nuclear reactor is given. These researches are necessary in the future to build a model of decontamination process for irradiated graphite. |
| Idioma: | russo |
| Publicado em: |
2016
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| Colecção: | Проблемы прочности, пластичности и усталостной долговечности современных конструкционных материалов |
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| Acesso em linha: | http://earchive.tpu.ru/handle/11683/30988 |
| Formato: | Recurso Electrónico Capítulo de Livro |
| KOHA link: | https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=619066 |